Published February 2002 | Version v1
Journal article

Hydrogen isotope retention and recycling in fusion reactor plasma-facing components

Description

The proper design of a fusion reactor is not possible unless there is an understanding of the hydrogen isotope retention and recycling for the plasma-facing components. From the tritium inventory point of view, it is absolutely necessary to understand the short-term and long-term hydrogen isotopes retention characteristics of the individual materials used for the first wall and divertor. From the plasma density and fueling point of view, it is necessary to understand the recycling characteristics of these materials. This report is an overview of the available data on hydrogen isotope retention and recycling for beryllium, tungsten, carbon, and selected liquid metals. For each material discussed, recommendations are made as to the most appropriate values to use for parameters such as diffusivity, solubility, recombination rate coefficient, and trapping

Additional details

Identifiers

PII
S0022311501007322;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
300
Journal Issue
2-3
Journal Page Range
p. 91-117
ISSN
0022-3115
CODEN
JNUMAM

INIS

Country of Publication
Netherlands
Country of Input or Organization
Israel
INIS RN
33063053
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
Descriptors DEI
BREEDING BLANKETS; DIFFUSION; DIVERTORS; FIRST WALL; PLASMA DENSITY; TRITIUM RECOVERY
Descriptors DEC
REACTOR COMPONENTS; THERMONUCLEAR REACTOR WALLS

Optional Information

Copyright
Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.